Boiling heat-exchange reinforced wall-attached orifice plate assembly shell component

Abstract

A boiling heat-exchange reinforced wall-attached orifice plate assembly shell component relates to the technical field of reinforced heat exchange. A wall-attached orifice plate assembly is mounted on an outer wall of a reactor pressure vessel and is supported and fixed by a fixing assembly, and is composed of a plurality of wall-attached orifice plate units mutually connected with each other as one. The wall-attached orifice plate units are orifice plate structure and are provided with a plurality of plate holes in an array arrangement. A plurality of wall-attached supporting members in the array arrangement are arranged at the inner side of the wall-attached orifice plate units, so that a gap is formed between part of the inner wall of the wall-attached orifice plate units except the supporting members and the outer wall of the reactor pressure vessel. The wall-attached orifice plate units are composed of orifice plates and connecting and strengthening side plates, and the connecting and strengthening side plates are arranged at edges of the orifice plates. The component can substantially reinforce boiling heat-exchange process, improve critical hot-fluid density, and thus substantially improve security; and strengthens heat exchange and improve performance stability of critical hot-fluid density.

Description

technical field [0001] The invention relates to the technical field of enhanced heat transfer, in particular to an enhanced boiling heat transfer assembly shell member with a wall-attached orifice plate, which is used for enhanced boiling heat transfer outside the spherical head of the pressure vessel of a large nuclear power reactor. Background technique [0002] Severe accidents in large nuclear power reactors may lead to core meltdown. Cooling and retaining the molten material in the reactor pressure vessel is a key measure to mitigate the accident. By filling the reactor chamber with water, submerging the hemispherical head at the bottom of the pressure vessel, and boiling the pool outside the pressure vessel, it is an important measure to mitigate severe accidents. Utilize the boiling heat transfer and passive natural circulation flow of the water outside the pressure vessel to remove the decay heat of the melt in the hemispherical head, thereby maintaining the integrit...

AI Technical Summary

Problems solved by technology

At present, the outer surface of the spherical head under the pressure vessel of a large nuclear power reactor generally adopts an ordinary smooth surface, that is, no enhanced heat transfer measures have been adopted at present. This is mainly because the pressure vessel equipment of a large nuclear power reactor is an ultra-large equipment, such as a 1000MW unit. The internal diameter of the reactor pressure vessel is 4m, and the weight of the pressure vessel is more than 400 tons. Therefore, it is very difficult to manufacture an enhanced heat exchange structure on the outer surface of the spherical head under such a super-large pressure vessel. The enhanced heat exchange measures adopted It may also have adverse effects on the strength and safety of the pressure vessel. Even if the heat exchange enhancement measures such as porous coatings and bulges are used, they are relatively easy to be damaged during transportation and installation, and they will be damaged during long-term operation. The reliability and effectiveness of the process are also difficult to control

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